ML20203K997
| ML20203K997 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 08/05/1986 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Sorensen E WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| Shared Package | |
| ML20203K999 | List: |
| References | |
| NUDOCS 8608220304 | |
| Download: ML20203K997 (6) | |
See also: IR 05000397/1986011
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION V
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1450 MARIA LANE,SulTE 210
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WALNUT CREEK, CALIFORNIA 94596
AUG 051986
Docket No. 50-397
Washington Public Power Supply System
P. O. Box 968
3000 George Washington Way
Richland, Washington 99352
Attention:
Mr. G. C. Sorensen, Manager
Regulatory Programs
Centlenen:
Subject: NRC INSPECTION OF WASHINGTON NUCLEAR PROJECT NO. 2
This refers to the special team inspection conducted by Mr. R. T. Dodds and
other members of our staff on June 16-27, 1986, of activities authorized by
NRC License No. NPF-21, and the discussion of our findings held by Mr. Dodds
with Mr. J. W. Shannon and other members of your staff at the conclusion of
the inspection.
Areas examined during this inspection are described in the enclosed inspection
report. Within these areas, the inspection consisted of selective
examinations of procedures and representative records, interviews with
personnel and other observations by the inspectors.
Based on the results of this inspection, it appears that certain of your
activities were not conducted in full compliance with NRC requirements.
Enforcement action by the NRC relating to the apparent violations of regulatory
requirements discussed in the attached report will be the subject of separate
correspondence.
This inspection focused its effort upon your programs and controls associated
with the Residual Heat Removal System, Standby Service Water System and the
Emergency Diesel Generatorr and the implementation and adherence of those
programs and controls in the following areas: Plant Operations; Operator
Recovery Actions; Technical Specification Surveillance Program; Maintenance
Programs; Plant Modifications; Design Changes; Past Maintenance and Past
Modification Testing and Quality Assurance / Quality Control Program.
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AUG 051986
Overall Conclusion
The apparent violations discussed in the enclosed report indicate that
management has not yet created the necessary atmosphere for performing
safety-related work or effectively communicated to the work force their
expectations. This conclusion is based on the number of violations involving:
(1) failure to perform work cctivities in accordance with approved instructions
and procedures; (2) repetitive nature of certain violations; and (3) a limited
quality control program that did not include prescribed criteria for
designating inspection requirements for certain types of maintenance
activities other than those prescribed by certain mandatory codes.
During the past year violations of similar nature have been brought to
the licensee's attention. The licensee's corrective actions for those past
items have apparently been ineffective to remedy the underlying problems
associated with ensuring that safety-related work activities are performed and
documented properly.
Areas Inspected and Results
Quality Assurance Surveillance and Quality Control
The onsite QA/QC group appears to have been given limited resources and the
scope of inspections are such that the effectiveness of the program is
questionable.
In several instances QA surveillance reports were inadequate
to show the efforts involved and contained errors and omissions. Actions to
correct identified deficiencies were on occasion untimely and OC inspection
requirements were generally determined solely by the QC group for corrective
maintenance. However, the maintenance foreman, among others, may call for a
particular inspection. Criteria had not been established to prescribe
inspection requirements for corrective maintenance other than those mandated
by applicable codes.
In addition, the value of the independence aspect of the QA/QC group appears
to be lessened by becoming overly sensitive to plant manaFement's priorities and
scheduling concerns as indicated by:
acceptance by QA of incomplete or inadequate commitments to correct
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deficiencies in a timely manner,
acceptance of delay in scheduled corrective action because of plant
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management priorities, and
excused missed commitments without obtaining documented alternates
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from plant management.
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G. C. Sorensen
AUG 051986
Corrective Maintenance
The licensee's maintenance program was examined by reviewing both the
corrective and preventive maintenance program. The effectiveness and control
of these maintenance programs were analyzed by reviewing completed maintenance
work requests (MWR).
The inspector determined that corrective action for a quality assurance
deficiency report on the maintenance work request (MWR) process was not
performed; and that problems stated by the deficiency still exist in the
documentation of the MWR's.
The inspector further identified an MWR which was
written for work on the motor operator of valve RHR-M0-6B and was amended,
after the MWR reviews were completed, to include work on the motor operator
for another valve, RHR-27B. Following this work, the MWR was not re-reviewed
by the maintenance group supervisor. The inspectors concluded that the
failure to initiate corrective action on the deficiency report and the failure
to implement the procedure appeared to be violations of regulatory
requirements.
Preventive Maintenance
The licensee's preventative maintenance program was examined by conducting an
intensive inspection of the Scheduled Maintenance System (SMS). Although the
inspection concentrated on the RHR system, the SSW system and diesel
generators preventative maintenance programs were also inspected.
The inspection included interviews with the individuals that implement the
program, a review of the procedures that are followed in running the SMS, a
comparison of how the program is carried out in three maintenance shops, a
review of maintenance records, and a walkdown of a day-to-day preventative
maintenance operation. Within this scope, two violatione were identified
pertaining to the lack of QC inspection and failure to follow procedures on
the installation of air start motors for the emergency diesel generators.
Maintenance Work Observation
The working conditions inside the cubical containing RHR-V-53B during the
overhaul of the valve lacked a proper environment for the control of safety
related work and personnel exposure and contamination control. Members of
management had visited the cubical and failed to question the existing
inadequate working conditions.
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AUG 051986
G. C. Sorensen
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Measuring and Test Equipment
The program for the control of Measuring and Test Equipment (M&TE) was
inspected to determine whether procedures were established and implemented to
assure that tools, gauges, instruments, and other measuring and testing
equipment used to calibrate and repair safety-related components and systems
were properly controlled, calibrated and adjusted to maintain precision and
accuracy within specified limits.
The control of Measuring and Test Equipment was not being implemented in
accordance with the approved program procedures. Specifically, items which
were supposed to be in the tool crib were missing, wire connector crimping
tools were not entered into the control list, and torque wrenches were out for
an extended period of time. These findings are similar to those identified
during the 1985 team inspections, for which enforcement action was taken.
It
appears that management's corrective actions were less than effective in
precluding recurrence of the situation. This is a repeat violation of
regulatory requirements in the area of M&TE.
Technical Specification Surveillance Program
The surveillance program was examined to assure that there existed a
responsible organization that administered the master schedule associated with
the surveillances required by the Technical Specifications.
Completed surveillances of the Residual Heat Removal, Standby Service Water
and Emergency Power systems were reviewed for completeness, timeliness and
test results. Generally, the program was found to be effective and well
implemented. There were, however, two areas that were not consistent with
program objectives; those being in the areas of performance trending and
station battery surveillance.
System Walkdown
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Walkdowns of the RHR system outside containment and an inspection inside
control room boards A, B and C, and control room panels 601, 602 and 603 were
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performed by the inspectors. Numerous examples of poor housekeeping and
presence of uncontrolled items inside electrical panels, which could cause
shorts of safety related circuits, were observed. Other items identified
included: missing and loose handwheels for instrument line and drain valves;
many overhead lights burned out; debris on floors and in RHR pump pit;
uncontrolled tonis; material blocking drain screens; etc. These items were
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brought to the licansee's attention. Accordingly, the licensee is requested
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to inspect inside til safety related electrical panels and remove all
uncontrolled items which could cause shorts.
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G. C. Sorensen
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AUG 051986
Operator Recovery Actions
The area of Operator Recovery Actions associated with the use and operation of
the Residual Heat Removal system (RHR) was examined. The level of operator
knowledge and understanding of the procedures used during emergencies that
involve use of the RHR system was found to be extensive. However, one item of
concern was identified related to the administrative control of approved
charts, and changes thereto, used in conjunction with the emergency
procedures.
Plant Modificatio-s
The design modification process at WNP-2 was reviewed to evaluate the adequacy
of the process with respect to the requirements of 10 CFR 50.59 and 10 CFR 50
Appendix B and to verify that sample design modification complied with the
written procedures that define the WNP-2 design modification program. The
design change program was found to provide adequate controls except in the
areas of post modification testing and independent reviews of MWR's that
implement quality modifications.
Emergency Procedures
The inspector reviewed the facility's emergency procedures in order to
ascertain whether their overall technical adequacy was consistent with desired
actions and modes of operation. The inspector also ascertained that emergency
procedures were in accordance with regulatory requirements. No areas of
concern were identified.
Plant Procedures
Administrative and system operating procedures pertaining to the RHR system
were reviewed against the FSAR and RHR flow diagrams. The procedures were
found to be adequate to control operations of the RHR system, but two valve
numbers needed to be removed from the Locked Valve Checklist, and nine valves
should be added. The licensee has agreed to'make these changes.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure
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will be placed in the NRC Public Document Room.
Should you have any questions concerning this inspection, we will be glad to
discuss them with you,
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Dennis F. K sch, Director
Division of Reactor Safety and Projects
Enclosure:
1.
Inspection Report No. 50-397/86-11
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cc w/ enclosures:
C. M. Powers, WPPSS
AUG 051986
P. L. Powell, WPPSS
R. B. Glasscock, WPPSS
J. D. Martin, WPPSS
G. E. Doupe, Esq., WPPSS
W. G. Conn, Burns & Roe, Inc.
State of WA
N. S. Reynolds, Esq., BLCP&R
C. J. Heltemes, AEOD
J. G. Partlow, IE
W. T. Russell, NRR
bec w/ enclosures:
Resident Inspector
Project Inspector
G. Cook
B. Faulkenberry
J. Martin
RSB/ Document Control Desk (RIDS)
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bec w/o enclosure 2:
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